ML20212H447

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Monthly Operating Rept for Dec 1986
ML20212H447
Person / Time
Site: San Onofre 
Issue date: 12/31/1986
From: Morgan H, Siacor E
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM)
References
NUDOCS 8701210427
Download: ML20212H447 (6)


Text

,

~ th NRC MONTHLY OPERATING REPORT DOCKET NO. 50-206 UNIT NAME SONGS - 1 DATE January 14, 1987 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 OPERATING STATUS 1.' Unit Name: San Onofre Nuclear Generating Station, Unit 1

2. Reporting Period: December 1986
3. Licensed Thermal Power (MWt):

1347

4. Nameplate Rating (Gross MWe):

456

5. Design Electrical Rating (Net MWe):

436 6.. Maximum Dependable Capacity (Gross MWe):

456

7. Maximum Dependable Capacity (Net MWe):

436

8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7)

Since Last Report, Give Reasons:

NA

9. Power Level To Which Restricted, If Any (Net MWe):

390

10. Reasons For Restrictions, If Any:

Self-imposed power level limit to control steam generator tube corrosion.

This Month Yr.-to-Date Cumulative

'11. Hours In Reporting Period 744.00 8,760.00 171,344.00

12. Number Of Hours Reactor Was Critical 690.30 2,975.33 99,078.62_
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Wours Generator On-Line 684.20 2,731.51 95,103.28
15. Unit Reserve Shutdown Hourr 0.00 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 836,207.35 2,995,681.81 120,305,908.86
17. Gross Electrical Energy Generated (MWH) 272,400.00 963,562.38 40,793,196.38
18. Net Electrical Energy Generated (MWH) 256,059.00 874,187.00 38,514,662.00
19. Unit Service Factor 91.96%

31.18%

55.50%

20. Unit Availability Factor 91.96%

31.18%

55.50%

21. Unit Capacity Factor (Using MDC Net) 78.94%

22.8_9%

51.55%

22. Unit Capacity Factor (Using DER Net)

O.00%

24.13%

21.21%

78.94%

22.89%

51.55%

23. Unit Forced Outage Rate
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Mid-Cycle outage-April 10, 1987, 45-day duration

25. If Shutdown At End Of Report Period, Estimated Date of Startup:

NA

26. Units In Test Status (Prior To Commercial Operation):

Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 7596u/3 8701210427 861231 PDR ADOCK 05000206 fI R

PDR

n

+

.f AVERAGE DAILY UNIT POWER LEVEL--

DOCKET NO.

50-206 J-UNIT SONGS - 1 DATE January 14, 1987 COMPLETED 8Y E. R. Stacor TELEPHONE

-(714) 368-6223 MONTH:

December 1986 i

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-N'et) '

1 385.24 17 379.65 2-384.76 18 379.13 3

384.76 19 383.92 4

383.26 20 384.37 5

. 383.78 21 384.39 i

6 384.06 22 384.01 7

383.92 23 384.74 8

- 383.89 24 ~

383.93

'9 384.01 25 383.78 t

10 384.34 26 384.36 l.

11 384.58 27 384.05

'12 359.00 28 385.05 13 0.00 29 385.25

.14 0.00 30 385.81

^

i~

15 48.07 31 386.30 l

16 363.85 1

7596u/4 l

3 UNIT SHUTDOWNS AND POWER REDUCTION 3 DOCKET NO. 50-206 UNIT NAME SONGS - 1 REPORT MONTH DECEMBER 1986 DATE.Tannarst 1A loa 7 COMPLETED BY E.

R.

S'i aco ?

TELEPHONE (714) 368-6223 Method of Shutting Down System Component Cause & Corrective 1

Du ra t ion J

3 LER 4

4 Action to No.

Date Type (Hours)

Reason Reactor No.

Code Code Prevent Recurrence 106 861213 S

59.80 B

1 NA CC HX Scheduled plant shutdown was initiated to repair Component Cooling Water Heat Exchanger (HX) E-208 sa l twa te r d i scha rge p i p i ng.

The rubber lining at a portion of the piping had peeled off and re st ric ted saltwater cooling flow to the heat exchanger. The portion of piping involved was replaced and the HX was returned to service.

1 2

3 4

F-Fo rced Reason:

Method:

IEEE Std. 803-1983 S-Scheduled A-Equipment Fa ilure (Expla in) 1-Manual B-Ma intenance or Test 2-Manual Sc ra m.

C-Refueling 3-Automatic Scram.

D-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination Previous Month F-Adm i n i s t ra t ive 5-Reduction of 20%

G-Ope ra t iona l Error (Explain) or Greater in the H-Othe r ( Exp la in)

Past 24 Hours 6-Other (Expla in) 7596u/5 e

4

+

ww-

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET 50-206 UNIT SONGS - 1 DATE January 14, 1987 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 DATE TIME EVENT December 1 0001 The Unit is in Mode 1 at 92% reactor power.

Turbine load at 404 MWe gross.

December 12 2100 Commenced Unit shutdown from 92% reactor power for a scheduled Component Cooling Water (CCW) Heat Exchanger (HX) E-208 saltwater cooling discharge piping repair.

December 13 0248 Entered Mode 2.

0250 Unit taken off line.

0318 Entered Mode 3.

December 15 0817.

Commenced Unit startup following completion of repairs to CCW HX E-20B saltwater cooling discharge piping.

0842 Entered Mode 2.

0900 Reactor made critical.

1314 Entered Mode 1.

1326 Turbine tripped on no load at low power. ' Entered Mode 2.

Reactor remained critical.

1500 Entered Mode 1 and synchronized Unit to the grid.

Continuing reactor power increase.

December 16 0730 Reactor power at 92%. Turbine-load at 398 MWe gross.

December 31 2400 The Unit is in Mode 1 at 92% reactor power "urbine load at 405 MWe gross.

7596u/6

o

-c REFUELING INFORMATION DOCKET NO.

50-206

^

UNIT SONGS

'1 DATE January 14. 1987 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223 MONTH:

December 1986' 1.

Scheduled date for next refueling shutdown.

March 1988-2.

Scheduled date for restart following refueling.

June 1988 3.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

Not yet determined What will these be?

~Not yet determined 4.

Scheduled date for_ submitting proposed licensing action and supporting information.

Not applicable

[

5.

Important Licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel desigr., new operating procedures.

(

None l

l 6.

The number of fuel assemblies.

a)

In the core.

157 b)

In the spent fuel storage pool.

146 7.

Licensed spent fuel storage capacity.

216 l

Intended change in spent fuel storage capacity. Under review

(

8.

Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

March 1988 7596u/7 i

l

?"d2?

as Southern California Edison Company SAN ONOFRE NUCLEAR GENERATING STATION P. O. BOX t 28 SAN CLEMENTE, CALIFORNIA 92672 H.E. MORGAN TELEPHONE

****2*'

January 14, 1987 STATION MANAGEa Document Control Desk U.S. Nucleae Regulatory Commission Washington, D.C.

20555

Subject:

Docket No. 50-206 Monthly Operating Report for December 1986 San Onofre Nuclear Generating Station, Unit 1 Enclosed is the Monthly Operating Report as required by Section 6.9.1.10 of Appendix A, Technical Specifications to Provisional Operating License DPR-13 for San Onofre Nuclear Generating Station, Unit 1.

Please contact us if we can be of further assistance.

Sincerely, MbM Enclosures cc:

J. B. Martin (Regional Administrator, USNRC Region V)

F. R. Huey (USNRC Senior Resident Inspector, Units 1, 2 and 3)

R. F. Dudley, Jr. (USNRC Unit 1 Project Manager, Office of Nuclear Reactor Regulation)

Institute of Nuclear Power Operations (INPO) u

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